Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme
The reactor pressure vessel (RPV) is the most critical component of every nuclear power plant (NPP) and continuous evaluation of its mechanical properties is a necessity for long and safe operation. Standard tests require a collection of large-dimension samples coming from the precious and archive m...
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| Format: | Article |
| Language: | English |
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Ubiquity Press
2018-09-01
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| Series: | Ubiquity Proceedings |
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| Online Access: | https://account.ubiquityproceedings.com/index.php/up-j-up/article/view/28 |
| _version_ | 1827379492655464448 |
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| author | M. Kapusňák J. Petzová M. Březina M. Adamech |
| author_facet | M. Kapusňák J. Petzová M. Březina M. Adamech |
| author_sort | M. Kapusňák |
| collection | DOAJ |
| description | The reactor pressure vessel (RPV) is the most critical component of every nuclear power plant (NPP) and continuous evaluation of its mechanical properties is a necessity for long and safe operation. Standard tests require a collection of large-dimension samples coming from the precious and archive materials, usually produced as control segments. Since SPT testing samples are quite small, high activity of irradiated materials is no longer an issue. The SPT technique therefore represents a very useful and effective method applied for characterization of mechanical properties such as ultimate tensile strength (Rm), yield strength (Re), and fracture appearance transition temperature (FATT). Monitoring of structural components in nuclear power plants receives much attention, particularly, in the context of long term operation (LTO) of current plants where the amount of material available for destructive testing is considerably limited. |
| first_indexed | 2024-03-08T13:17:28Z |
| format | Article |
| id | doaj.art-8f51f8f52135408b9c2b50ed1f83b0dc |
| institution | Directory Open Access Journal |
| issn | 2631-5602 |
| language | English |
| last_indexed | 2024-03-08T13:17:28Z |
| publishDate | 2018-09-01 |
| publisher | Ubiquity Press |
| record_format | Article |
| series | Ubiquity Proceedings |
| spelling | doaj.art-8f51f8f52135408b9c2b50ed1f83b0dc2024-01-18T05:31:39ZengUbiquity PressUbiquity Proceedings2631-56022018-09-011S1282810.5334/uproc.2825Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen ProgrammeM. Kapusňák0J. Petzová1M. Březina2M. Adamech3VUJE, a.s., Okružná 5, 918 64 Trnava, SlovakiaVUJE, a.s., Okružná 5, 918 64 Trnava, SlovakiaVUJE, a.s., Okružná 5, 918 64 Trnava, SlovakiaVUJE, a.s., Okružná 5, 918 64 Trnava, SlovakiaThe reactor pressure vessel (RPV) is the most critical component of every nuclear power plant (NPP) and continuous evaluation of its mechanical properties is a necessity for long and safe operation. Standard tests require a collection of large-dimension samples coming from the precious and archive materials, usually produced as control segments. Since SPT testing samples are quite small, high activity of irradiated materials is no longer an issue. The SPT technique therefore represents a very useful and effective method applied for characterization of mechanical properties such as ultimate tensile strength (Rm), yield strength (Re), and fracture appearance transition temperature (FATT). Monitoring of structural components in nuclear power plants receives much attention, particularly, in the context of long term operation (LTO) of current plants where the amount of material available for destructive testing is considerably limited.https://account.ubiquityproceedings.com/index.php/up-j-up/article/view/28reactor pressure vesselsmall punch testsurveillance specimen programmeirradiation |
| spellingShingle | M. Kapusňák J. Petzová M. Březina M. Adamech Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme Ubiquity Proceedings reactor pressure vessel small punch test surveillance specimen programme irradiation |
| title | Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme |
| title_full | Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme |
| title_fullStr | Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme |
| title_full_unstemmed | Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme |
| title_short | Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme |
| title_sort | interim results of the reactor pressure vessel materials evaluation within the framework of the implemented advanced surveillance specimen programme |
| topic | reactor pressure vessel small punch test surveillance specimen programme irradiation |
| url | https://account.ubiquityproceedings.com/index.php/up-j-up/article/view/28 |
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